ES2078946T3 - AUTOMATIC MONITOR OF THERMAL LIMITS. - Google Patents

AUTOMATIC MONITOR OF THERMAL LIMITS.

Info

Publication number
ES2078946T3
ES2078946T3 ES90306864T ES90306864T ES2078946T3 ES 2078946 T3 ES2078946 T3 ES 2078946T3 ES 90306864 T ES90306864 T ES 90306864T ES 90306864 T ES90306864 T ES 90306864T ES 2078946 T3 ES2078946 T3 ES 2078946T3
Authority
ES
Spain
Prior art keywords
flow
limits
thermal
atlm
block
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Lifetime
Application number
ES90306864T
Other languages
Spanish (es)
Inventor
Fred Chia-Chi Chao
William Stewart Rowe
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
General Electric Co
Original Assignee
General Electric Co
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by General Electric Co filed Critical General Electric Co
Application granted granted Critical
Publication of ES2078946T3 publication Critical patent/ES2078946T3/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/08—Regulation of any parameters in the plant
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

UN MODELO CALCULADO DE DISTRIBUCION EN ESPACIO DE POTENCIA DISPONIBLE DEL REACTOR SE LEE PERIODICAMENTE A LA MEMORIA DEL ORDENADOR BASADA EN EL MICROPROCESADOR Y SE RETIENE EN MEMORIA EN TRES MATRICES DIMENSIONALES. ESTA RETENCION SE PRODUCE ENTRE ACTUALIZACIONES REGULARES DEL ORDEN DE CADA DOS MINUTOS. EL REACTOR ESTA CONVENCIONALMENTE MONITORIZADO EN GRUPOS DE 16 PAQUETES DE COMBUSTIBLE CADA UNO. CADA GRUPO DE 16 PAQUETES SE MONITORIZA EN CUANTO A SU FLUJO DE NEUTRONES TERMICOS MEDIANTE CUATRO CADENAS VERTICALES DE MONITORES DE GAMA LOCAL DE POTENCIA, TENIENDO CADA CADENA UNO DE LOS CUATRO MONITORES DE POTENCIA SITUADO EN CUATRO ELEVACIONES DIFERENTES, QUE EXTIENDEN LA ALTURA DEL NUCLEO ACTIVO. CADA GRUPO DE PAQUETES SE CONTROLA POR CUATRO VARILLAS DE MANDO Y SE DA POR SENTADO QUE ESTA SUJETO A CAMBIO UNIFORME DE FLUJO CON CAMBIO DE FLUJO DEL REACTOR TOTAL. EL MONITOR DE LIMITE TERMICO AUTOMATIZADO (ATLM) TOMA COMO ENTRADAS TODA LA INFORMACION DEL MONITOR DE GAMA DE POTENCIAS PROCEDENTE DEL NUCLEO DEL REACTOR BWR SOBRE UNA BASE CONTINUA A DOS CANALES, UNO DE LOS CUALES PARA DETERMINAR LOS LIMITES OPERATIVOS Y EL OTRO PARA DETERMINAR LOS LIMITES DE SEGURIDAD. ESTAS SEÑALES SE PROCESAN DENTRO DEL SISTEMA, DE CONFORMIDAD CON DIFERENTES REQUERIMIENTOS ALGORITMICOS PARA LA PROTECCION DE LOS LIMITES TERMICOS DE COMBUSTIBLE, ES DECIR, AMPLIFICACION CRITICA MINIMA (MCPR) Y ESTIMACION DE TERMOGENERACION LINEAL MAXIMA (MLHGR). EL SISTEMA TOMA TAMBIEN COMO ENTRADA LOS LIMITES DE PARAMETROS TERMICOS DE NUCLEO ABSOLUTOS ON-LINE, JUNTAMENTE CON UN CONJUNTO DE PARAMETROS INCORPORADOS LLAMADOS FACTORES A Y B, QUE SON FUNCIONES DE POTENCIA DE NUCLEO, Y POSICION DE VARILLAS DE CONTROL, Y LOS DATOS LIMITE TERMICOS OPERATIVOS EN LAS CONDICIONES DE FLUJO Y POTENCIA DE CORRIENTE. BASADO EN LA INFORMACION ANTERIOR, EL SISTEMA CALCULA VALORES DE PUNTOS DE REFERENCIA DE SEÑALES PARA MCPR Y MLHGR RESPECTIVAMENTE. ESTOS VALORES DE PUNTOS DE REFERENCIAS SE COMPARAN CON LAS SEÑALES ATLM INSTANTANEAMENTE EXAMINADAS CONTINUAMENTE PARA DETERMINAR SI DEBE EMITIRSE UN COMANDO DE BLOQUE DE RETIRADA DE VARILLAS DE CONTROL O UN COMANDO DE BLOQUE DE FLUJO DE NUCLEO. SI UN VALOR DE SEÑAL ATLM PROCESADO Y EXPLORADO SE APROXIMA A SU PUNTO DE REFERENCIA, ENTONCES SE EMITE EL BLOQUE DE VARILLAS (O BLOQUE DE FLUJO). ASI SE ASEGURA ENTONCES QUE LOS LIMITES TERMICOS DEL NUCLEO NO SE VIOLAN SOBRE LA RETIRADA DE VARILLAS O CAMBIOS DE FLUJO. ESTE DESCUBRIMIENTO DE LA INVENCION NO DESCRIBE SOLAMENTE LA CONFIGURACION DEL SISTEMA Y LOGICA FUNCIONAL DEL BLOQUE DE VARILLAS Y BLOQUE DE FLUJO, TAMBIEN DESCRIBE LAS BASES DEL DISEÑO DE LOS FACTORES A Y B EN EL ALGORITMO DEL SISTEMA, QUE SON FUNDAMENTALES AL SISTEMA TOTAL ATLM. EL CONCEPTO DE LA CONFIGURACION, LA LOGICA FUNCIONAL Y LA FORMA Y EL DISEÑO DE LOS FACTORES A Y B CONSTITUYEN LA PARTE PRINCIPAL DEL DESCUBRIMIENTO DE LA INVENCION DEL DISEÑO ATLM.A CALCULATED MODEL OF DISTRIBUTION IN POWER SPACE AVAILABLE FROM THE REACTOR IS PERIODICALLY READ TO THE COMPUTER MEMORY BASED ON THE MICROPROCESSOR AND IS RETAINED IN MEMORY IN THREE DIMENSIONAL MATRICES. THIS RETENTION OCCURS BETWEEN REGULAR UPDATES OF THE ORDER OF EVERY TWO MINUTES. THE REACTOR IS CONVENTIONALLY MONITORED IN GROUPS OF 16 FUEL PACKAGES EACH ONE. EACH GROUP OF 16 PACKAGES IS MONITORED AS TO ITS FLOW OF THERMAL NEUTRONS THROUGH FOUR VERTICAL CHAINS OF LOCAL RANGE MONITORS, EACH CHAIN HAS ONE OF THE FOUR ACTIVE MONITORS DELIVERED IN FOUR ELEVATIONS, DIFFERENT DIFFERENT DIFFERENT ELEVATIONS DIFFERENT . EACH GROUP OF PACKAGES IS CONTROLLED BY FOUR CONTROL RODS AND IT IS ASSUMED THAT IT IS SUBJECT TO UNIFORM CHANGE OF FLOW WITH CHANGE OF FLOW OF THE TOTAL REACTOR. THE AUTOMATED THERMAL LIMIT MONITOR (ATLM) TAKES ALL THE INFORMATION OF THE POWER RANGE MONITOR FROM THE BWR REACTOR CORE ON A CONTINUOUS BASE WITH TWO CHANNELS, ONE OF WHICH TO DETERMINE THE OPERATIONAL LIMITS AND THE OTHER TO DETERMINE SECURITY LIMITS. THESE SIGNALS ARE PROCESSED WITHIN THE SYSTEM, IN ACCORDANCE WITH DIFFERENT ALGORITHMIC REQUIREMENTS FOR THE PROTECTION OF THERMAL FUEL LIMITS, THAT IS, MINIMUM CRITICAL AMPLIFICATION (MCPR) AND ESTIMATION OF MAXIMUM LINEAR THERMOGENERATION (MLHGR) THE SYSTEM ALSO TAKES THE LIMITS OF ABSOLUTE ON-LINE NUCLEO THERMAL PARAMETERS AS AN INPUT, TOGETHER WITH A SET OF INCORPORATED PARAMETERS CALLED FACTORS A AND B, WHICH ARE NUCLEO POWER FUNCTIONS, AND DATOS POSITIONS. IN THE CONDITIONS OF FLOW AND CURRENT POWER. BASED ON THE ABOVE INFORMATION, THE SYSTEM CALCULATES SIGNAL REFERENCE POINT VALUES FOR MCPR AND MLHGR RESPECTIVELY. THESE REFERENCE POINT VALUES ARE COMPARED TO THE ATLM SIGNALS INSTANTLY REVIEWED CONTINUOUSLY TO DETERMINE WHETHER A CONTROL ROD REMOVAL BLOCK COMMAND OR A NUCLEO FLOW BLOCK COMMAND SHOULD BE ISSUED. IF A PROCESSED AND EXPLORED ATLM SIGNAL VALUE APPROACHES ITS REFERENCE POINT, THEN THE ROD BLOCK (OR FLOW BLOCK) IS ISSUED. THEREFORE IT IS ENSURE THAT THE THERMAL LIMITS OF THE CORE ARE NOT VIOLATED ON THE REMOVAL OF RODS OR CHANGES OF FLOW. THIS DISCOVERY OF THE INVENTION DOES NOT DESCRIBE ONLY THE SYSTEM CONFIGURATION AND FUNCTIONAL LOGIC OF THE ROD BLOCK AND FLOW BLOCK, ALSO DESCRIBES THE DESIGN BASES OF FACTORS A AND B, WHICH ARE FUNDAMENTAL TO THE SISTEMATICALLY SISTEMATICAL ALGORITHM. THE CONCEPT OF THE CONFIGURATION, THE FUNCTIONAL LOGIC AND THE FORM AND DESIGN OF THE FACTORS A AND B CONSTITUTE THE MAIN PART OF THE DISCOVERY OF THE ATLM DESIGN INVENTION.

ES90306864T 1989-06-26 1990-06-22 AUTOMATIC MONITOR OF THERMAL LIMITS. Expired - Lifetime ES2078946T3 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US07/371,365 US5091139A (en) 1989-06-26 1989-06-26 Automated thermal limit monitor

Publications (1)

Publication Number Publication Date
ES2078946T3 true ES2078946T3 (en) 1996-01-01

Family

ID=23463680

Family Applications (1)

Application Number Title Priority Date Filing Date
ES90306864T Expired - Lifetime ES2078946T3 (en) 1989-06-26 1990-06-22 AUTOMATIC MONITOR OF THERMAL LIMITS.

Country Status (5)

Country Link
US (1) US5091139A (en)
EP (1) EP0405863B1 (en)
JP (1) JPH0769451B2 (en)
DE (1) DE69022305T2 (en)
ES (1) ES2078946T3 (en)

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US5930779A (en) * 1997-03-25 1999-07-27 Mci Communications Corporation Web based system and method to automate storage of power plant data and calculation of battery reserves
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US5912933A (en) * 1997-12-04 1999-06-15 General Electric Company Method and system for direct evaluation of operating limit minimum critical power ratios for boiling water reactors
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US6611572B2 (en) * 2000-12-29 2003-08-26 Global Nuclear Fuel - Americas, L.L.C. Determination of operating limit minimum critical power ratio
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US20030086520A1 (en) * 2001-11-07 2003-05-08 Russell William Earl System and method for continuous optimization of control-variables during operation of a nuclear reactor
US7487133B2 (en) * 2002-09-19 2009-02-03 Global Nuclear Fuel - Americas, Llc Method and apparatus for adaptively determining weight factors within the context of an objective function
FR2846139B1 (en) * 2002-10-21 2005-02-18 Framatome Anp METHOD FOR DETERMINING A LIMIT VALUE OF AN OPERATING PARAMETER OF A NUCLEAR REACTOR, PROGRAM AND SUPPORT THEREFOR
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JP4594819B2 (en) * 2005-07-29 2010-12-08 株式会社東芝 Control rod pull-out monitoring device
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US7366273B2 (en) * 2005-12-30 2008-04-29 General Electric Company Method of determining margins to operating limits for nuclear reactor operation
US8842802B2 (en) * 2006-10-16 2014-09-23 Global Nuclear Fuel-Americas, Llc. Fuel rods for nuclear reactor fuel assemblies and methods of manufacturing thereof
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ES2545179T3 (en) 2007-10-10 2015-09-09 Westinghouse Electric Sweden Ab Procedures and devices related to a light water nuclear reactor of the boiling water type
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US8433029B2 (en) * 2007-12-14 2013-04-30 Global Nuclear Fuel—Americas, LLC Determination of safety limit minimum critical power ratio
JP5191342B2 (en) * 2008-10-09 2013-05-08 中国電力株式会社 Reactor control rod pull-out monitoring device
FR2946454B1 (en) * 2009-06-08 2011-07-22 Areva Np METHOD FOR DETERMINING NUCLEAR REACTOR LIMITATIONS FOR PREVENTING DAMAGE BY PASTILLE-SHEAR INTERACTION
JP2012150088A (en) * 2011-01-21 2012-08-09 Toshiba Corp Oscillation power range monitor and soundness confirmation method therefor
US20130266107A1 (en) 2012-03-16 2013-10-10 Westinghouse Electric Company Llc Methods for protection of nuclear reactors from thermal hydraulic/neutronic core instability
US20140376678A1 (en) * 2013-06-25 2014-12-25 Robert H. Leyse Method of and Apparatus for Monitoring a Nuclear Reactor Core Under Normal and Accident Conditions
JP6453262B2 (en) * 2016-03-09 2019-01-16 日立Ｇｅニュークリア・エナジー株式会社 Control rod operation monitoring method and control rod operation monitoring system
FR3053150B1 (en) 2016-06-22 2020-09-18 Areva Np METHOD OF CALCULATING AN IPG MARGIN ASSOCIATED WITH A NUCLEAR REACTOR LOADING PLAN, ASSOCIATED SYSTEM, COMPUTER PROGRAM AND SUPPORT
FR3075449B1 (en) * 2017-12-18 2020-01-10 Areva Np METHOD FOR DETERMINING AT LEAST ONE LIMIT VALUE OF AT LEAST ONE OPERATING PARAMETER OF A NUCLEAR REACTOR, COMPUTER PROGRAM AND RELATED ELECTRONIC SYSTEM
KR102034830B1 (en) * 2018-01-05 2019-10-21 한국수력원자력 주식회사 Method of monitoring for regional overpower protection detector
CN109215820B (en) * 2018-08-14 2019-11-26 中广核核电运营有限公司 Nuclear power plant evaporator Steam-water Flow Measurement channel comparative approach and system
CN109243641B (en) * 2018-10-18 2022-04-22 中国核动力研究设计院 Reactor pressure vessel experiment simulator for loss of coolant accident of pressurized water reactor
CN113421676B (en) * 2021-06-18 2022-05-10 中国核动力研究设计院 Method and device for determining accident procedure setting value of nuclear power plant
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Also Published As

Publication number Publication date
US5091139A (en) 1992-02-25
JPH0365693A (en) 1991-03-20
DE69022305D1 (en) 1995-10-19
JPH0769451B2 (en) 1995-07-31
DE69022305T2 (en) 1996-04-04
EP0405863A3 (en) 1991-11-21
EP0405863A2 (en) 1991-01-02
EP0405863B1 (en) 1995-09-13

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